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Influence of Radiation-Stimulated Grain-Boundary Segregation of Phosphorus on the Operational Properties of Nuclear-Reactor-Vessel Materials
The main mechanisms of radiation embrittlement of reactor vessel materials are considered to be hardening of material as a result of the formation of matrix defects, for example, micropores and second-phase precipitates - copper and others, and a change in the cohesive strength of grain boundaries a...
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Published in: | Atomic energy (New York, N.Y.) N.Y.), 2001-11, Vol.91 (5), p.884-895 |
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Main Authors: | , , , |
Format: | Article |
Language: | English |
Subjects: | |
Citations: | Items that cite this one |
Online Access: | Get full text |
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Summary: | The main mechanisms of radiation embrittlement of reactor vessel materials are considered to be hardening of material as a result of the formation of matrix defects, for example, micropores and second-phase precipitates - copper and others, and a change in the cohesive strength of grain boundaries as a result of the segregation of surface-active impurities, primarily, phosphorus. The question of the degree to which the latter mechanism affects the change in the properties of reactor-vessel materials under irradiation remains open. In the present paper, computational estimates of the kinetics of radiation-stimulated segregation of phosphorus on grain boundaries in reactor-vessel materials and the resulting changes in the mechanical characteristics of steel are compared with corresponding experimental data.[PUBLICATION ABSTRACT] |
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ISSN: | 1063-4258 1573-8205 |
DOI: | 10.1023/A:1014257605632 |